To assess the safety for disposal of radioactive mortar-waste composition, the leaching of Cs-137, Co-60 and Sr-85 from immobilized radioactive evaporator concentrate, into a surrounding fluid has been studied. This paper also presents results from studies made to determine the influence of natural sorbents (bentonite and zeolite) on immobilization of evaporator concentrate in cement matrix, by measuring leachability of Cs-137, Co-60 and Sr-85. Leaching tests were carried out in accordance with a method recommended by IAEA, under 300 days. From the leaching data the apparent diffusivity of cobalt, cesium and strontium in cement-bentonite matrix with a waste load of 701 kg/m(3) evaporator concentrate was measured. The uniaxial compressive strength of 11 mortar samples is determined following the ASTM standards. These results are part of a 30-year mortar and concrete testing project which will influence the design of radioactive waste management for a future Serbian radioactive waste dis...posal center. (C) 2005 Elsevier Ltd. All rights reserved.
TY - JOUR
AU - Plećaš, Ilija B.
AU - Dimović, Slavko
AU - Smičiklas, Ivana D.
PY - 2006
UR - http://vinar.vin.bg.ac.rs/handle/123456789/3077
AB - To assess the safety for disposal of radioactive mortar-waste composition, the leaching of Cs-137, Co-60 and Sr-85 from immobilized radioactive evaporator concentrate, into a surrounding fluid has been studied. This paper also presents results from studies made to determine the influence of natural sorbents (bentonite and zeolite) on immobilization of evaporator concentrate in cement matrix, by measuring leachability of Cs-137, Co-60 and Sr-85. Leaching tests were carried out in accordance with a method recommended by IAEA, under 300 days. From the leaching data the apparent diffusivity of cobalt, cesium and strontium in cement-bentonite matrix with a waste load of 701 kg/m(3) evaporator concentrate was measured. The uniaxial compressive strength of 11 mortar samples is determined following the ASTM standards. These results are part of a 30-year mortar and concrete testing project which will influence the design of radioactive waste management for a future Serbian radioactive waste disposal center. (C) 2005 Elsevier Ltd. All rights reserved.
T2 - Progress in Nuclear Energy
T1 - Utilization of bentonite and zeolite in cementation of dry radioactive evaporator concentrate
VL - 48
IS - 6
SP - 495
EP - 503
DO - 10.1016/j.pnucene.2005.12.001
ER -
@article{
author = "Plećaš, Ilija B. and Dimović, Slavko and Smičiklas, Ivana D.",
year = "2006",
url = "http://vinar.vin.bg.ac.rs/handle/123456789/3077",
abstract = "To assess the safety for disposal of radioactive mortar-waste composition, the leaching of Cs-137, Co-60 and Sr-85 from immobilized radioactive evaporator concentrate, into a surrounding fluid has been studied. This paper also presents results from studies made to determine the influence of natural sorbents (bentonite and zeolite) on immobilization of evaporator concentrate in cement matrix, by measuring leachability of Cs-137, Co-60 and Sr-85. Leaching tests were carried out in accordance with a method recommended by IAEA, under 300 days. From the leaching data the apparent diffusivity of cobalt, cesium and strontium in cement-bentonite matrix with a waste load of 701 kg/m(3) evaporator concentrate was measured. The uniaxial compressive strength of 11 mortar samples is determined following the ASTM standards. These results are part of a 30-year mortar and concrete testing project which will influence the design of radioactive waste management for a future Serbian radioactive waste disposal center. (C) 2005 Elsevier Ltd. All rights reserved.",
journal = "Progress in Nuclear Energy",
title = "Utilization of bentonite and zeolite in cementation of dry radioactive evaporator concentrate",
volume = "48",
number = "6",
pages = "495-503",
doi = "10.1016/j.pnucene.2005.12.001"
}
Plećaš IB, Dimović S, Smičiklas ID. Utilization of bentonite and zeolite in cementation of dry radioactive evaporator concentrate. Progress in Nuclear Energy. 2006;48(6):495-503
Plećaš, I. B., Dimović, S.,& Smičiklas, I. D. (2006). Utilization of bentonite and zeolite in cementation of dry radioactive evaporator concentrate.
Progress in Nuclear Energy, 48(6), 495-503.
https://doi.org/10.1016/j.pnucene.2005.12.001
Plećaš Ilija B., Dimović Slavko, Smičiklas Ivana D., "Utilization of bentonite and zeolite in cementation of dry radioactive evaporator concentrate" 48, no. 6 (2006):495-503,
https://doi.org/10.1016/j.pnucene.2005.12.001 .
